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MONTHYEARML0216800682002-07-10010 July 2002 Environmental Assessment Revised Final Safety Evaluation Report Licensing Basis for the Post-Accident Operation of the Supplementary Leakage Collection and Release System Project stage: Approval ML0224703992002-09-16016 September 2002 License Amendment, Revise Final Safety Analysis Report Licensing Basis for Post-Accident Operation of Supplementary Leakage Collection & Release System Project stage: Other ML0232905682002-11-25025 November 2002 Correction to Safety Evaluation (SE) for Amendment No. 211 Project stage: Approval 2002-07-10
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Category:Environmental Assessment
MONTHYEARML20332A1392020-12-0707 December 2020 Documentation of Completion of Required Actions Taken in Response to Lessons Learned from the Fukushima Dai-Ichi Accident ML19165A1202019-06-14014 June 2019 Enclosuenvironmental Assessment and Finding of No Significant Impact for the Virginia Electric and Power Company, Dominion Energy Kewaunee, Inc., and Dominion Nuclear Connecticut, Inc.'S Decommissioning Funding Plans Submitted ML17212A0012017-09-19019 September 2017 Letter Enclosing Environmental Assessment and Finding of No Significant Impact ML12212A2502012-08-13013 August 2012 Environmental Assessment and Finding of No Significant Impact Optimized Zirlo Fuel Rod Cladding Materials ML1213205742012-06-27027 June 2012 Environmental Assessment and Finding of No Significant Impact ML1213205762012-06-27027 June 2012 Environmental Assessment and Finding of No Significant Impact ML11138A0202011-08-22022 August 2011 Environmental Assessment and Finding of No Significant Impact ML1003304222010-03-19019 March 2010 Environmental Assessment and Finding of No Significant Impact ML1001311152010-01-12012 January 2010 Request for Exemptions from 10 CFR 73.55 Power Reactor Security Requirements Final Rule Additional Information ML0819300702008-07-30030 July 2008 Final Environmental Assessment and Finding of No Significant Impact for Proposed Stretch Power Uprate ML0808704572008-05-29029 May 2008 Draft Environmental Assessment and Finding of No Significant Impact for Proposed Stretch Power Uprate ML0634902692007-01-11011 January 2007 Memo: K. Mcconnell to M. Lesar - Notice of Environmental Assessment and Finding of No Significant Impact Related to Partial Exemption from 10 CFR Part 50, Recordkeeping Requirements - Millstone Power Station, Unit 1 ML0432202762005-02-0808 February 2005 Environmental Assessment and Finding of No Significant Impact ML0332303792003-12-22022 December 2003 Environmental Assessment, Environmental Assessment and Finding of No Significant Impact Related to Exemption from Requirements of Title 10 of the Code of Federal Regulations, Section 54.17(c) ML0322000272003-10-0202 October 2003 Environmental Assessment and Finding of No Significant Impact Related to Exemption from Requirements of 10 CFR 50.44, 10 CFR 50.46, and 10 CFR Part 50, Appendix K ML0216800682002-07-10010 July 2002 Environmental Assessment Revised Final Safety Evaluation Report Licensing Basis for the Post-Accident Operation of the Supplementary Leakage Collection and Release System ML0205703072002-04-0808 April 2002 Environmental Assessment Revised Final Safety Evaluation Report Analysis of a Steam Generator Tube Rupture (Tac No. MB0866) ML0201802002002-01-18018 January 2002 Environmental Assessment, TAC Nos. MB2874, MB2875 and MB2876 Physical Protection License Condition and Site Name 2020-12-07
[Table view] Category:Finding of No Significant Impact
MONTHYEARML17212A0012017-09-19019 September 2017 Letter Enclosing Environmental Assessment and Finding of No Significant Impact ML12212A2502012-08-13013 August 2012 Environmental Assessment and Finding of No Significant Impact Optimized Zirlo Fuel Rod Cladding Materials ML1213205762012-06-27027 June 2012 Environmental Assessment and Finding of No Significant Impact ML11138A0202011-08-22022 August 2011 Environmental Assessment and Finding of No Significant Impact ML1003304222010-03-19019 March 2010 Environmental Assessment and Finding of No Significant Impact ML0808704572008-05-29029 May 2008 Draft Environmental Assessment and Finding of No Significant Impact for Proposed Stretch Power Uprate ML0634902692007-01-11011 January 2007 Memo: K. Mcconnell to M. Lesar - Notice of Environmental Assessment and Finding of No Significant Impact Related to Partial Exemption from 10 CFR Part 50, Recordkeeping Requirements - Millstone Power Station, Unit 1 ML0432202762005-02-0808 February 2005 Environmental Assessment and Finding of No Significant Impact ML0332303792003-12-22022 December 2003 Environmental Assessment, Environmental Assessment and Finding of No Significant Impact Related to Exemption from Requirements of Title 10 of the Code of Federal Regulations, Section 54.17(c) ML0322000272003-10-0202 October 2003 Environmental Assessment and Finding of No Significant Impact Related to Exemption from Requirements of 10 CFR 50.44, 10 CFR 50.46, and 10 CFR Part 50, Appendix K ML0216800682002-07-10010 July 2002 Environmental Assessment Revised Final Safety Evaluation Report Licensing Basis for the Post-Accident Operation of the Supplementary Leakage Collection and Release System ML0201802002002-01-18018 January 2002 Environmental Assessment, TAC Nos. MB2874, MB2875 and MB2876 Physical Protection License Condition and Site Name 2017-09-19
[Table view] Category:Letter
MONTHYEARML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24260A2192024-09-16016 September 2024 Decommissioning Trust Fund Disbursement - Revision to Previous Thirty-Day Written Notification ML24260A1952024-09-16016 September 2024 Response to Request for Additional Information Regarding Proposed Amendment to Support Implementation of Framatome Gaia Fuel ML24248A2272024-09-0404 September 2024 Operator Licensing Examination Approval ML24240A1532024-09-0303 September 2024 Summary of Regulatory Audit Supporting the Review of License Amendment Request for Implementation of Framatome Gaia Fuel IR 05000336/20240052024-08-29029 August 2024 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Reports 05000336/2024005 and 05000423/2024005 IR 05000336/20240022024-08-13013 August 2024 Integrated Inspection Report 05000336/2024002 and 05000423/2024002 ML24221A2872024-08-0808 August 2024 Independent Spent Fuel Storage Installation (ISFSI) - Submittal of Cask Registration for Spent Fuel Storage IR 05000336/20244412024-08-0606 August 2024 Supplemental Inspection Report 05000336/2024441 and 05000423/2024441 and Follow-Up Assessment Letter (Cover Letter Only) ML24212A0742024-08-0505 August 2024 Request for Withholding Information from Public Disclosure - Millstone Power Station, Unit No. 3, Proposed Alternative Request IR-4-13 to Support Steam Generator Channel Head Drain Modification ML24211A1712024-07-25025 July 2024 Associated Independent Spent Fuels Storage Installation, Revision to Emergency Plan - Report of Change IR 05000336/20244032024-07-22022 July 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000336/2024403 and 05000423/2024403 IR 05000336/20245012024-07-0101 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000336/2024501 and 05000423/2024501 ML24180A0932024-06-28028 June 2024 Readiness for Additional Inspection: EA-23-144 IR 05000336/20240102024-06-26026 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000336/2024010 and 05000423/2024010 ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 IR 05000336/20244402024-06-24024 June 2024 Final Significance Determination for Security-Related Greater than Green Finding(S) with Assessment Follow-up; IR 05000336/2024440 and 05000423/2024440 and Notice of Violation(S), NRC Investigation Rpt 1-2024-001 (Cvr Ltr Only) ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML24162A0882024-06-10010 June 2024 Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications ML24165A1292024-06-0505 June 2024 ISFSI, 10 CFR 50.59 Annual Change Report for 2023 Annual Regulatory Commitment Change Report for 2023 ML24128A2772024-06-0404 June 2024 Issuance of Amendment No. 290 to Revise TSs for Reactor Core Safety Limits, Fuel Assemblies, and Core Operating Limits Report for Use of Framatome Gaia Fuel (EPID L-2023-LLA-0074) (Non-Proprietary) ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24110A0562024-05-21021 May 2024 Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2023-LLE-0013) (Letter) ML24109A0032024-05-21021 May 2024 Issuance of Amendment No. 289 to Revise Technical Specifications to Use Framatome Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limit (EPID L-2023-LLA-0065) (Non-Proprietary) ML24141A2432024-05-20020 May 2024 Response to Request for Additional Information Regarding Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment No. 15 ML24141A1502024-05-20020 May 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications ML24142A0952024-05-20020 May 2024 End of Cycle 22 Steam Generator Tube Inspection Report IR 05000336/20240012024-05-14014 May 2024 Integrated Inspection Report 05000336/2024001 and 05000423/2024001 and Apparent Violation ML24123A2272024-05-0202 May 2024 Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications ML24123A2042024-05-0202 May 2024 Pre-Decisional Replay to EA-23-144 IR 05000336/20244012024-04-30030 April 2024 Security Baseline Inspection Report 05000336/2024401 and 05000423/2024401 (Cover Letter Only) ML24123A1222024-04-30030 April 2024 Inservice Inspection Program - Owners Activity Report, Refueling Outage 22 ML24116A0452024-04-25025 April 2024 Special Inspection Follow-Up Report 05000336/2024440 and 05000423/2024440 and Preliminary Finding(S) of Greater than Very Low Significance and NRC Investigation Report No. 1-2024-001 (Cover Letter Only) ML24116A1742024-04-24024 April 2024 Annual Radiological Environmental Operating Report ML24114A2662024-04-24024 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report ML24103A0202024-04-22022 April 2024 Summary of Regulatory Audit in Support of License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits ML24106A2032024-04-15015 April 2024 2023 Annual Environmental Operating Report ML24088A3302024-04-0404 April 2024 Regulatory Audit Plan in Support of License Amendment Request to Implement Framatome Gaia Fuel ML24093A1022024-04-0101 April 2024 Alternative Request IR-4-13, Proposed Alternative Request to Support Steam Genera Tor Channel Head Drain Modification ML24093A2162024-04-0101 April 2024 Response to Request for Additional Information Regarding License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits IR 05000336/20240112024-04-0101 April 2024 Comprehensive Engineering Team Inspection - Inspection Report 05000336/2024011 and 05000423/2024011 ML24092A0752024-03-28028 March 2024 3R22 Refueling Outage Inservice Inspection (ISI) Owners Activity Report Extension ML24088A2352024-03-26026 March 2024 Decommissioning Funding Status Report ML24086A4762024-03-22022 March 2024 Application for Technical Specification Change to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line-Item Improvement Process ML24086A4802024-03-22022 March 2024 Alternative Request IR-4-14, Proposed Alternative Request to Defer ASME Code Section XI Inservice Inspection Examination for Pressurizer and Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles ML24051A1922024-03-0808 March 2024 – Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) IR 05000336/20230062024-02-28028 February 2024 Annual Assessment Letter for Millstone Power Station, Units 2 and 3, (Reports 05000336/2023006 and 05000423/2023006) ML24053A2632024-02-21021 February 2024 Unit 3, and Independent Spent Fuel Storage Installation, Notification Pursuant to 10 CFR 72.212(b)(1) Prior to First Storage of Spent Fuel Under a General License ML24057A0612024-02-19019 February 2024 and Virgil C. Summer Power Nuclear Stations - Nuclear Property Insurance Coverage 2024-09-04
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July 10, 2002 Mr. J. A. Price Site Vice President - Millstone Dominion Nuclear Connecticut, Inc.
c/o Mr. David A. Smith Rope Ferry Road Waterford, CT 06385
SUBJECT:
MILLSTONE NUCLEAR POWER STATION, UNIT NO. 3 - ENVIRONMENTAL ASSESSMENT RE: REVISED FINAL SAFETY EVALUATION REPORT LICENSING BASIS FOR THE POST-ACCIDENT OPERATION OF THE SUPPLEMENTARY LEAKAGE COLLECTION AND RELEASE SYSTEM (TAC NO. MB3700)
Dear Mr. Price:
Enclosed is a copy of the Environmental Assessment and Finding of No Significant Impact related to your application for amendment dated June 6,1998, as supplemented by letters dated April 5, 1999; April 7, April 19, July 31, and September 28, 2000; March 19, June 11, September 21, and December 20, 2001. The proposed amendment would revise the licensing basis for the post-accident operation of the Supplementary Leakage Collection and Release System as described in the Millstone Nuclear Power Station, Unit No. 3, Final Safety Analysis Report.
The assessment is being forwarded to the Office of the Federal Register for publication.
Sincerely,
/RA/
Victor Nerses, Sr. Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-423
Enclosure:
Environmental Assessment cc w/encl: See next page
July 10, 2002 Mr. J. A. Price Site Vice President - Millstone Dominion Nuclear Connecticut, Inc.
c/o Mr. David A. Smith Rope Ferry Road Waterford, CT 06385
SUBJECT:
MILLSTONE NUCLEAR POWER STATION, UNIT NO. 3 - ENVIRONMENTAL ASSESSMENT RE: REVISED FINAL SAFETY EVALUATION REPORT LICENSING BASIS FOR THE POST-ACCIDENT OPERATION OF THE SUPPLEMENTARY LEAKAGE COLLECTION AND RELEASE SYSTEM (TAC NO. MB3700)
Dear Mr. Price:
Enclosed is a copy of the Environmental Assessment and Finding of No Significant Impact related to your application for amendment dated June 6,1998, as supplemented by letters dated April 5, 1999; April 7, April 19, July 31, and September 28, 2000; March 19, June 11, September 21, and December 20, 2001. The proposed amendment would revise the licensing basis for the post-accident operation of the Supplementary Leakage Collection and Release System as described in the Millstone Nuclear Power Station, Unit No. 3, Final Safety Analysis Report.
The assessment is being forwarded to the Office of the Federal Register for publication.
Sincerely,
/RA/
Victor Nerses, Sr. Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-423
Enclosure:
Environmental Assessment cc w/encl: See next page DISTRIBUTION:
PUBLIC PDI-2 R/F SRichards JClifford TClark VNerses JTappert OGC ACRS CCowgill, RI Accession Number: ML021680068 OFFICE PDI-2/PM PDI-2/LA RLEP/SC OGC PDI-2/SC NAME VNerses TClark AKugler for JTappert SUttal JZimmerman for JClifford DATE 6/18/02 6/18/02 6/20/02 6/27/02 7/10/02 OFFICIAL RECORD COPY
Millstone Nuclear Power Station Unit 3 cc:
Ms. L. M. Cuoco Mr. Evan W. Woollacott Senior Nuclear Counsel Co-Chair Dominion Nuclear Connecticut, Inc. Nuclear Energy Advisory Council Rope Ferry Road 128 Terrys Plain Road Waterford, CT 06385 Simsbury, CT 06070 Edward L. Wilds, Jr., Ph.D. Mr. D. A. Christian Director, Division of Radiation Senior Vice President - Nuclear Operations Department of Environmental Protection and Chief Nuclear Officer 79 Elm Street Innsbrook Technical Center - 2SW Hartford, CT 06106-5127 5000 Dominion Boulevard Waterford, CT 06385 Regional Administrator, Region I U.S. Nuclear Regulatory Commission Mr. C. J. Schwarz 475 Allendale Road Director -Nuclear Station Operations King of Prussia, PA 19406 and Maintenance Dominion Nuclear Connecticut, Inc.
First Selectmen Rope Ferry Road Town of Waterford Waterford, CT 06385 15 Rope Ferry Road Waterford, CT 06385 Senior Resident Inspector Millstone Nuclear Power Station Mr. P. J. Parulis c/o U.S. Nuclear Regulatory Commission Manager - Nuclear Oversight P. O. Box 513 Dominion Nuclear Connecticut, Inc. Niantic, CT 06357 Rope Ferry Road Waterford, CT 06385 Mr. G. D. Hicks Director - Nuclear Station Safety Mr. W. R. Matthews and Licensing Vice President and Senior Dominion Nuclear Connecticut, Inc.
Nuclear Executive - Millstone Rope Ferry Road Dominion Nuclear Connecticut, Inc. Waterford, CT 06385 Rope Ferry Road Waterford, CT 06385 Mr. J. Alan Price Site Vice President - Millstone Ernest C. Hadley, Esquire c/o Mr. David A. Smith P.O. Box 1104 Dominion Nuclear Connecticut, Inc.
West Falmouth, MA 02574-1104 Rope Ferry Road Waterford, CT 06385 Mr. John Markowicz Co-Chair Nuclear Energy Advisory Council 9 Susan Terrace Waterford, CT 06385
Millstone Nuclear Power Station Unit 3 cc:
Mr. D. A. Smith Manager - Licensing Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Ms. Nancy Burton 147 Cross Highway Redding Ridge, CT 00870 Mr. William D. Meinert Nuclear Engineer Massachusetts Municipal Wholesale Electric Company P.O. Box 426 Ludlow, MA 01056 Mr. S. E. Scace Director - Nuclear Engineering Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. M. J. Wilson Manager - Nuclear Training Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385
7590-01-P UNITED STATES NUCLEAR REGULATORY COMMISSION DOMINION NUCLEAR CONNECTICUT, INC.
DOCKET NO. 50-423 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 3 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an amendment to Title 10 of the Code of Federal Regulations (10 CFR) Part 50 for Facility Operating License No. NPF-49 issued to Dominion Nuclear Connecticut, Inc. (the licensee), for operation of the Millstone Nuclear Power Station, Unit No. 3 (MP3), located in Waterford, Connecticut. Therefore, as required by 10 CFR 51.21, the NRC is issuing this environmental assessment and finding of no significant impact.
ENVIRONMENTAL ASSESSMENT Identification of the Proposed Action:
The proposed action would revise the Final Safety Analysis Report (FSAR) description of the Supplementary Leakage Collection and Release System (SLCRS) operation after a postulated accident. As a result, this revision modifies the licensing basis for the post-accident operation of the SLCRS.
The proposed action is in accordance with the licensees application dated June 6, 1998, as supplemented by letters dated April 5, 1999; April 7, April 19, July 31, and September 28, 2000; March 19, June 11, September 21, and December 20, 2001.
The Need for the Proposed Action:
The proposed action is necessary because the SLCRS is used to maintain a negative pressure relative to atmospheric in the secondary containment by collecting air from the enclosure building and connecting areas, filtering it to remove iodine, and discharging the filtered air to the atmosphere. The licensee has identified potential release pathways from secondary containment to the environment that could bypass the SLCRS filter following a design-basis accident due to non-nuclear safety-grade (NNS) exhaust fan operation after the accident. These additional pathways are not included in the current design-basis accident dose analyses as documented in the MP3 FSAR, therefore making them non-conservative. The proposed action would include the additional pathway in the current design-basis accident dose analyses.
Environmental Impacts of the Proposed Action:
The NRC has completed its evaluation of the proposed action and concludes that issuance of the proposed amendment would not have a significant environmental impact. The proposed changes to the FSAR provide documentation of a combination of events not previously included in the FSAR. Based on the licensees use of acceptable methodologies and assumptions, and staff confirmation of the licensees dose results, the staff has determined that the licensees revised design-basis accident radiological consequences analyses for the Loss of Coolant Accident (LOCA) and rod ejection accident, which take into account additional SLCRS bypass release pathways, are acceptable. The analyses show that the radiological consequences of a postulated design-basis LOCA are within 10 CFR Part 100 dose limits for offsite doses and 10 CFR Part 50, Appendix A, General Design Criterion 19, dose limits with regard to control room habitability.
The proposed action will not significantly increase the probability or consequences of accidents, no changes are being made in the types of effluents that may be released off site,
and there is no significant increase in occupational or public radiation exposure. Therefore, there are no significant radiological environmental impacts associated with the proposed action.
With regard to potential nonradiological impacts, the proposed action does not have a potential to affect any historic sites. It does not affect nonradiological plant effluents and has no other environmental impact. Therefore, there are no significant nonradiological environmental impacts associated with the proposed action.
Accordingly, the NRC concludes that there are no significant environmental impacts associated with the proposed action.
Environmental Impacts of the Alternatives to the Proposed Action:
As an alternative to the proposed action, the staff considered denial of the proposed action (i.e., the "no-action" alternative). Denial of the application would result in no change in current environmental impacts. The environmental impacts of the proposed action and the alternative action are similar.
Alternative Use of Resources:
The action does not involve the use of any different resource than those previously considered in the Final Environmental Statement for MP3, dated December 1984.
Agencies and Persons Consulted:
On June 12, 2002, the staff consulted with the Connecticut State official, Mr. Michael Firsick of the Connecticut Department of Environmental Protection, regarding the environmental impact of the proposed action. The State official had no comments.
FINDING OF NO SIGNIFICANT IMPACT On the basis of the environmental assessment, the NRC concludes that the proposed action will not have a significant effect on the quality of the human environment. Accordingly, the NRC has determined not to prepare an environmental impact statement for the proposed action.
For further details with respect to the proposed action, see the licensees letter dated June 6, 1998, as supplemented by letters dated April 5, 1999; April 7, April 19, July 31, and September 28, 2000; March 19, June 11, September 21, and December 20, 2001. Documents may be examined, and/or copied for a fee, at the NRCs Public Document Room (PDR), located at One White Flint North, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly available records will be accessible electronically from the Agencywide Documents Access and Management System (ADAMS) Public Electronic Reading Room on the internet at the NRC Web site, http://www.nrc.gov/reading-rm/adams.html. Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS should contact the NRC PDR Reference staff by telephone at 1-800-397-4209 or 301-415-4737, or by e-mail to pdr@nrc.gov.
Dated at Rockville, Maryland, this 10th day of July 2002.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Victor Nerses, Sr. Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation